JournalTOCs

Nuclear Science and Engineering
Journal Prestige (SJR): 0.92

Citation Impact (citeScore): 1
Number of Followers: 7

Hybrid journal * Containing 21 Open Access article(s) in this issue *
ISSN (Print) 0029-5639 - ISSN (Online) 1943-748X
Published by Taylor and Francis

[2652 journals]

The Virtual Test Bed (VTB) Repository: A Library of Reference Reactor
Models Using NEAMS Tools
Open Access Article
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  Authors: Guillaume L. Giudicelli, Abdalla Abou-Jaoude, April J. Novak, Ahmed Abdelhameed, Paolo Balestra, Lise Charlot, Jun Fang, Bo Feng, Thomas Folk, Ramiro Freile, Thomas Freyman, Derek Gaston, Logan Harbour, Thanh Hua, Wen Jiang, Nicolas Martin, Yinbin Miao, Jason Miller, Isaac Naupa, Dan O’Grady, David Reger, Emily Shemon, Nicolas Stauff, Mauricio Tano, Stefano Terlizzi, Samuel Walker, Cody Permann
  Pages: 1 - 17
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-23T08:11:19Z
  DOI: 10.1080/00295639.2022.2142440
Thermal-Hydraulic Investigation of Steady-State Single-Phase Natural
Circulation of an Integral PWR-Type SMR Test Rig (iPSTR)
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  Authors: Muhammad Ishaq, Muhammad Ilyas, Alam Nawaz Khan Wardag, Muhammad Zaman, Mansoor H. Inayat
  Pages: 1 - 29
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-23T02:11:07Z
  DOI: 10.1080/00295639.2022.2139565
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron Induced
Fission of 229Th
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  Authors: H. Naik, R. J. Singh, S. P. Dange, W. Jang
  Pages: 1 - 14
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-23T02:08:42Z
  DOI: 10.1080/00295639.2022.2150029
Influence of Quantum Oscillations in the Thermal Scattering Law of
Zirconium Carbide on Neutron Thermalization and Criticality
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  Authors: J. L. Wormald, J. C. Holmes, M. L. Zerkle
  Pages: 1 - 14
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-23T02:04:50Z
  DOI: 10.1080/00295639.2022.2138063
Discrete-Time Bayesian Networks Applied to Flexible Coping Strategies of
Nuclear Power Plant Systems
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  Authors: Elvan Sahin, Victor C. Leite, Kyung M. Kim, Nick Burns, Juliana Pacheco Duarte
  Pages: 1 - 18
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-19T05:30:28Z
  DOI: 10.1080/00295639.2022.2151300
Thermal-Hydraulic Analysis of the AFIP-7 Irradiation Test in the Advanced
Test Reactor—Oxide Growth Prediction and Correlation
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  Authors: Changhu Xing, Casey J. Jesse, Warren F. Jones, Maxine P. Johnson, Ann Marie Phillips, Theron D. Marshall
  Pages: 1 - 12
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-19T05:29:28Z
  DOI: 10.1080/00295639.2022.2153599
Application of Accelerator Beam Dumps for Dark Matter Searches
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  Authors: Patrick Achenbach, Mirco Christmann
  Pages: 1 - 6
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-19T05:28:29Z
  DOI: 10.1080/00295639.2022.2151301
A Generalized Eigenvalue Formulation for Core-Design Applications
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  Authors: Nicolo’ Abrate, Sandra Dulla, Piero Ravetto, Paolo Saracco
  Pages: 1 - 25
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-17T01:15:34Z
  DOI: 10.1080/00295639.2022.2134685
myMUSCLE, a New Multiphysics, Multiscale Simulation Coupling Environment
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  Authors: H. J. Uitslag-Doolaard, K. Zwijsen, F. Roelofs, M. M. Stempniewicz
  Pages: 1 - 18
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-12T01:24:21Z
  DOI: 10.1080/00295639.2022.2148809
Analyses of Critical Hydrogen Enrichment in PWR Containment Compartments
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  Authors: E. Schmidt, N. Reinke, M. Freitag, M. Sonnenkalb
  Pages: 1 - 13
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-12T01:20:35Z
  DOI: 10.1080/00295639.2022.2146994
A Quasi–Monte Carlo Method With Krylov Linear Solvers for Multigroup
Neutron Transport Simulations
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  Authors: Sam Pasmann, Ilham Variansyah, C. T. Kelley, Ryan McClarren
  Pages: 1 - 15
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-12T01:19:53Z
  DOI: 10.1080/00295639.2022.2143704
State of the Art in Cyclotrons for Radionuclide Production in Biomedicine
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  Authors: Mario Marengo, Gianfranco Cicoria, Angelo Infantino, Sara Vichi, Federico Zagni, Domiziano Mostacci
  Pages: 1 - 11
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-11T02:57:51Z
  DOI: 10.1080/00295639.2022.2146433
Geometry Extension and Assemblywise Domain Decomposition of nTRACER for
Direct Whole-Core Calculation of VVERs
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  Authors: Seongchan Kim, Han Gyu Joo
  Pages: 1 - 20
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-11T02:56:05Z
  DOI: 10.1080/00295639.2022.2144083
Multiphysics Analysis System for Heat Pipe Cooled Micro Reactors Employing
PRAGMA-OpenFOAM-ANLHTP
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  Authors: Jaeuk Im, Myung Jin Jeong, Namjae Choi, Kyung Min Kim, Hyoung Kyu Cho, Han Gyu Joo
  Pages: 1 - 15
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-11T02:55:51Z
  DOI: 10.1080/00295639.2022.2143209
Post-Neutron Mass Yield Distribution in the Thermal Neutron Induced
Fission of 233U
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  Authors: H. Naik, S. P. Dange, R. J. Singh, W. Jang
  Pages: 1 - 26
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-11T02:52:46Z
  DOI: 10.1080/00295639.2022.2142433
Review of the Fluid Dynamics and Heat Transport Phenomena in Packed Pebble
Bed Nuclear Reactors
Open Access Article
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  Authors: Rahman S. Almusafir, Ahmed A. Jasim, Muthanna H. Al-Dahhan
  Pages: 1 - 37
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-10T01:40:23Z
  DOI: 10.1080/00295639.2022.2146993
Wigner-Wilkins Neutron/Nucleus Scattering Kernel Quantum Mechanically
Derived
Open Access Article
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  Authors: J. A. Grzesik
  Pages: 1 - 9
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-10T01:38:56Z
  DOI: 10.1080/00295639.2022.2138064
Nonconforming Three-Dimensional Model for PWR Control Rod Movements
Without Homogenization and Cusping Effect
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  Authors: F. Filiciotto, E. Masiello, S. Cochet-Lapuerta, R. Lenain
  Pages: 1 - 21
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-09T03:23:12Z
  DOI: 10.1080/00295639.2022.2151783
A Novel Core Design with Movable Moderator for a Fluoride
Salt–Cooled High-Temperature Reactor
Open Access Article
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  Authors: Zuolong Zhu, Dean Wang, Valmor de Almeida, Charles Forsberg, Eugene Shwageraus
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-05T03:36:39Z
  DOI: 10.1080/00295639.2022.2146436
Study of Reactor Core Loading Monitoring at the GUINEVERE Facility
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  Authors: A. Bailly, J.-L. Lecouey, A. Billebaud, S. Chabod, A. Kochetkov, A. Krása, F.-R. Lecolley, G. Lehaut, N. Marie, N. Messaoudi, G. Vittiglio, J. Wagemans
  Pages: 1 - 11
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2023-01-05T02:40:30Z
  DOI: 10.1080/00295639.2022.2148813
Technical Reviewers
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  Abstract: Volume 197, Issue 1, JANUARY 2023, Page iii-v
  .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-12T07:37:39Z
  DOI: 10.1080/00295639.2023.2156210
  Issue No: Vol. 197, No. 1 (2022)
Feynman-α Analysis Using BGO Gamma-Ray Detector in a University
Training and Research Reactor
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  Authors: Masaki Goto, Tadafumi Sano, Kunihiro Nakajima, Takashi Kanda, Atsushi Sakon, Kengo Hashimoto
  Pages: 1 - 9
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-22T07:12:15Z
  DOI: 10.1080/00295639.2022.2143707
Numerical Investigation on the Thermal-Hydraulic Characteristics near a
Corroded Lower Head of the Reactor Vessel During IVR-ERVC
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  Authors: Cheng Peng, Youya Song, Jian Deng, Sen Mao, Jiang Wu
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-21T04:37:56Z
  DOI: 10.1080/00295639.2022.2143208
Capability Extension of the High-Resolution Thermal-Hydraulic Code ESCOT
for Hexagonal Geometry Core Multiphysics Analysis
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  Authors: Jorge Gonzalez-Amoros, Marianna Papadionysiou, Seongchan Kim, Han Gyu Joo
  Pages: 1 - 22
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-21T04:36:07Z
  DOI: 10.1080/00295639.2022.2140577
Post-Neutron Mass Yield Distribution in the Thermal Neutron Induced
Fission of 235U
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  Authors: H. Naik, S. P. Dange, R. J. Singh, W. Jang
  Pages: 1 - 25
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-21T04:35:57Z
  DOI: 10.1080/00295639.2022.2133947
High-Fidelity Neutron Transport Solution of High Temperature Gas-Cooled
Reactor by Three-Dimensional Linear Source Method of Characteristics
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  Authors: Kaijie Zhu, Boran Kong, Han Zhang, Jiong Guo, Fu Li
  Pages: 1 - 23
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-16T02:34:54Z
  DOI: 10.1080/00295639.2022.2143706
Euler-Euler Model of Bubbly Flow Using Particle-Center-Averaging Method
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  Authors: Hongmei Lyu, Fabian Schlegel, Roland Rzehak, Dirk Lucas
  Pages: 1 - 18
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-16T02:32:09Z
  DOI: 10.1080/00295639.2022.2131344
Deep Subcriticality Determination Using the Source Jerk Integral Method in
the SALMON Program
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  Authors: A. Kochetkov, A. Krása, N. Messaoudi, G. Vittiglio, J. Wagemans, A. Bailly, A. Billebaud, S. Chabod, F. -R. Lecolley, J. -L. Lecouey, G. Lehaut, N. Marie
  Pages: 1 - 9
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-16T02:31:24Z
  DOI: 10.1080/00295639.2022.2146429
Pressurized Water Reactor Core Power Control Using BAS-RBF-PID Approach
During Transient Operation
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  Authors: Derjew Ayele Ejigu, Xiaojing Liu
  Pages: 1 - 16
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-16T02:27:57Z
  DOI: 10.1080/00295639.2022.2138688
Parametric Model-Order Reduction for Radiation Transport Simulations Based
on an Affine Decomposition of the Operators
Open Access Article
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  Authors: Patrick Behne, Jan Vermaak, Jean Ragusa
  Pages: 1 - 29
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-15T08:10:29Z
  DOI: 10.1080/00295639.2022.2112901
Computational Fluid Dynamics Analysis of an Open-Pool Nuclear Research
Reactor Core for Fluid Flow Optimization Using a Channel Box
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  Authors: N. L. Scuro, G. Angelo, E. Angelo, M. H. A. Piro, P. E. Umbehaun, W. M. Torres, D. A. Andrade
  Pages: 1 - 17
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-15T08:10:17Z
  DOI: 10.1080/00295639.2022.2142437
Variance Reduction and Noise Source Sampling Techniques for Monte Carlo
Simulations of Neutron Noise Induced by Mechanical Vibrations
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  Authors: Hunter Belanger, Davide Mancusi, Amélie Rouchon, Andrea Zoia
  Pages: 1 - 24
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-09T05:05:46Z
  DOI: 10.1080/00295639.2022.2126719
Numerical Simulation of Sub-cooled Flow Boiling in a Vertical Annulus
Channel Under Near Atmospheric Pressure Conditions
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  Authors: Sachin Tom, P. Mangarjuna Rao, B. Venkatraman, S. Raghupathy
  Pages: 1 - 33
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-09T02:32:22Z
  DOI: 10.1080/00295639.2022.2133948
Introduction of the Adding and Doubling Method for Solving Bateman
Equations for Nuclear Fuel Depletion
Open Access Article
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  Authors: Olin W. Calvin, Barry D. Ganapol, R. A. Borrelli
  Pages: 1 - 31
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-09T02:30:07Z
  DOI: 10.1080/00295639.2022.2129950
Using a Random Forest Model to Choose Optimized Group Structures
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  Authors: Thomas G. Saller, Vishnu Nair, Andrew Till, Nathan Gibson
  Pages: 1 - 19
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-09T02:29:27Z
  DOI: 10.1080/00295639.2022.2133940
Variable Dynamic Mode Decomposition For Estimating Time Eigenvalues in
Nuclear Systems
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  Authors: Ethan Smith, Ilham Variansyah, Ryan McClarren
  Pages: 1 - 10
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-06T03:52:33Z
  DOI: 10.1080/00295639.2022.2142025
Compensated Feed water Pump Control Analysis of Effect of Base-Load
Electricity Demand Reduction on Nuclear Steam Supply System
Open Access Article
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  Authors: Frederick Agyemang, Stephen Yamoah, Seth Kofi Debrah
  Pages: 1 - 12
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-12-05T07:21:01Z
  DOI: 10.1080/00295639.2022.2132102
An Improved Dual Asymmetric Penalized Least Squares Baseline Correction
Method for High-Noise Spectral Data Analysis
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  Authors: Shuangbao Shu, Ziqiao Yu, Jiaxin Zhang, Zhiqiang Chen, Huajun Liang, Jingjing Chen
  Pages: 1 - 12
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-11-21T03:55:24Z
  DOI: 10.1080/00295639.2022.2132101
OpenFOAM-Hybrid: A Morphology Adaptive Multifield Two-Fluid Model
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  Authors: Fabian Schlegel, Richard Meller, Benjamin Krull, Ronald Lehnigk, Matej Tekavčič
  Pages: 1 - 14
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-11-21T03:53:20Z
  DOI: 10.1080/00295639.2022.2120316
Core Concept of Small Rotational Fuel-Shuffling Breed-and-Burn Fast
Reactor with Nitride Fuel and Sodium Coolant
Open Access Article
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  Authors: Tsendsuren Amarjargal, Jun Nishiyama, Toru Obara
  Pages: 1 - 8
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-11-18T03:34:02Z
  DOI: 10.1080/00295639.2022.2129952
State-of-the-Art in Evaluation Approaches for Risk Assessment of Insider
Threats to Nuclear Facility Physical Protection Systems
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  Authors: Chris Faucett, Karen Vierow Kirkland
  Pages: 1 - 12
  Abstract: .
  
  Citation: Nuclear Science and Engineering
  PubDate: 2022-11-18T03:34:01Z
  DOI: 10.1080/00295639.2022.2130635
Convergence Properties of a Linear Diffusion-Acceleration Method for
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Physics-Informed Neural Network Method and Application to Nuclear Reactor
Calculations: A Pilot Study
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Experimental Analysis of Fast-Transient Flow Boiling in Various Flow
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Investigation of the Inhomogeneous Mechanical and Crack Driving Force of
Low Alloy Steel SA508 and Its Welded 309L/308L Stainless Steel Cladding
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Correction
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LQG/LTR Controller Design for Power Control of Small Pressurized Water
Reactors Under Four Feedback-Controlled Strategies
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Analysis of Integral Experiment of the AHWR Critical Facility with
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Mixcoatl Software (Part 2): Verification of 1D Fluid Flow Methods Coupled
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Radiolytic Production of Fluorine Gas from MSR Relevant Fluoride Salts
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Possible Does Not Mean Useful: The Role of Probability of Attack in
Security Risk Management
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Effects of Vent Size and Wind on Dispersion of Hydrogen Leaked in a
Partially Open Space: Studies by Numerical Analysis
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Bayesian Estimation of Cross-Section, Experimental Error, and Calculation
Error: Comparison with Bias Factor Method
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An Analysis of Transport Effects in Steady-State Simulation of the Molten
Salt Reactor Experiment
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Quantification of Deep Neural Network Prediction Uncertainties for VVUQ of
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The NILO-CMFD Method for Iteratively Solving Coupled Neutron
Transport–Thermal Hydraulics Problems
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A Limited-Memory Framework for Conditional Point Sampling for Radiation
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New Security Concepts for Advanced Reactors
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A Dynamic Risk Framework for the Physical Security of Nuclear Power Plants
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Flow-Induced Vibrations of Two Flexible Tubes in Cross Flow
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Hybrid Variable Selection for Estimating Nominal HEPs and PIF Multipliers
for Digital Control Rooms
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An Inline Burnup Algorithm
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Numerical Caseology by Lagrange Interpolation for the 1D Neutron Transport
Equation in a Slab
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Measurements of the 27Al(α,n) Thick Target Yield near Threshold
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  Authors: K. Brandenburg, G. Hamad, Z. Meisel, C. R. Brune, D. E. Carter, J. Derkin, D. C. Ingram, Y. Jones-Alberty, B. Kenady, T. N. Massey, M. Saxena, D. Soltesz, S. K. Subedi, J. Warren
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Methods for Calculating Neutron Transfer Probabilities Between Assemblies
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Computing Physical Security System Effectiveness at Commercial Reactors
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A CFD Modeling Coupled with VOF Method and Solidification Model for Molten
Jet Breakup at Low Velocity
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Improvements in Antineutrino Spectrum by Including Fission Product
Corrections and Calculation of Scatter-based Pulse Height Distributions
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Computational Analysis of Thermal Striping in Primary Sodium System of
Liquid Metal Fast Breeder Reactor Using Finite Volume Method
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Monte Carlo Source Convergence Acceleration by Hybrid Multi-group and
Continuous Energy Neutron Transport
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  Authors: Valeria Raffuzzi, Eugene Shwageraus, Lee Morgan, Paul Cosgrove
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A Multigroup Homogeneous Flux Reconstruction Method Based on the
ANOVA-HDMR Decomposition
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  Authors: Pavel M. Bokov, Danniell Botes, Rian H. Prinsloo, Djordje I. Tomašević
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Development, Verification, and Validation of an Advanced Systems Code
KP-SAM for Kairos Power Fluoride Salt-Cooled High-Temperature Reactor
(KP-FHR)
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  Authors: Haihua Zhao, Lambert Fick, Alexander Heald, Quan Zhou, Samuel Richesson, Noah Sutton, Brandon Haugh
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Simulation of the High Temperature Test Facility (HTTF) Core Using the 2D
Ring Model with SAM
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  Authors: Zhiee Jhia Ooi, Thanh Hua, Ling Zou, Rui Hu
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Identifying Thermodynamic Mechanisms Affecting Reactor Pressure Vessel
Integrity During Severe Nuclear Accidents Simulated by Laser Heating at
the Laboratory Scale
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A Perspective on Data-Driven Coarse Grid Modeling for System Level Thermal
Hydraulics
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  Authors: Arsen S. Iskhakov, Cheng-Kai Tai, Igor A. Bolotnov, Nam T. Dinh
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  PubDate: 2022-09-08T07:08:01Z
  DOI: 10.1080/00295639.2022.2107864
Simulation of the Axial-Flow Centrifugal Bubble Separator for
Liquid-Fueled Molten Salt Reactors Using Eulerian Two-Fluid Model
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A Unified Framework of Stabilized Finite Element Methods for Solving the
Boltzmann Transport Equation
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  Authors: Qingming He, Chao Fang, Liangzhi Cao, Haoyu Zhang
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  PubDate: 2022-09-07T06:00:38Z
  DOI: 10.1080/00295639.2022.2106733
Simulation of the Melting Behavior of the UO2-Zircaloy Fuel Cladding
System by Laser Heating
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  Authors: L. Soldi, D. Manara, D. Bottomley, D. Robba, L. Luzzi, R. J. M. Konings
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  PubDate: 2022-09-07T06:00:25Z
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Post-Neutron Fission Product Yield Distribution in the Spontaneous Fission
of 244Cm
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  PubDate: 2022-09-06T05:16:02Z
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Numerical Investigations of Molten Salt Pump Journal Bearings Under
Hydrodynamic Lubrication Conditions for FHRs
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  Authors: Yuqi Liu, Shuai Che, Adam Burak, Daniel L. Barth, Nicolas Zweibaum, Minghui Chen
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-08-30T08:22:11Z
  DOI: 10.1080/00295639.2022.2103343
Uncertainty Quantification of a Light Water Pulsed-Neutron Die-Away
Experiment to Thermal Neutron Scattering Laws
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  Authors: Daniel Siefman, Mathieu Hursin, Catherine Percher, David Heinrichs
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-08-30T08:21:48Z
  DOI: 10.1080/00295639.2022.2103344
Beta-Ray-Bremsstrahlung Contributions to Short-Lived Delayed Photoneutron
Groups in Heavy Water Reactors
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  Authors: Yanuar Ady Setiawan, Hemantika Sengar, Douglas A. Fynan, Arief Rahman Hakim
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-08-30T08:19:55Z
  DOI: 10.1080/00295639.2022.2103341
Thermal-Hydraulic System-Level Analysis of a Molten Salt Natural
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  Authors: Sheng Zhang, Hsun-Chia Lin, Xiaodong Sun
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  PubDate: 2022-08-25T02:15:41Z
  DOI: 10.1080/00295639.2022.2102389
A Stochastic Transport Model for the Cumulative Number of Fissions and
Deposited Fission Energy
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  Authors: Anil K. Prinja, Patrick F. O’Rourke
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-08-25T02:07:05Z
  DOI: 10.1080/00295639.2022.2087830
Infiltration and Evaporation in Multiplying Porous Media and Associated
Criticality Phenomena
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  Authors: M. M. R. Williams
  Pages: 1 - 28
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-08-22T02:43:41Z
  DOI: 10.1080/00295639.2022.2103336
Development of an Activity Transport Model and in situ Measurements on
Deposited Radionuclides in the Primary Coolant Pipelines of the Chinshan
Nuclear Power Plant
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  Authors: Yu-Hung Shih, Mei-Ya Wang, Tsuey-Lin Tsai, Tsung-Kuang Yeh
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-08-22T02:38:28Z
  DOI: 10.1080/00295639.2022.2102392
Comparisons of Supercritical Loop Flow and Heat Transfer Behavior Under
Uniform and Nonuniform High-Flux Heat Inputs
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  Authors: Dong Yang, Lin Chen, Yongchang Feng, Haisheng Chen
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-08-16T03:15:07Z
  DOI: 10.1080/00295639.2022.2102391
Effect of Internal Decay Power and Surface Cooling on Nuclear Fuel Droplet
Solidification during MFCI in a SFR – A Numerical Study
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  Authors: M. Chandra Kumar, A. Jasmin Sudha, V. Subramanian, S. Athmalingam, B. Venkatraman
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-08-16T03:10:20Z
  DOI: 10.1080/00295639.2022.2103338
Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled
Fast Molten Salt Reactors
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  Authors: Yeongshin Jeong, Koroush Shirvan, Michael Buric
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-08-05T05:02:16Z
  DOI: 10.1080/00295639.2022.2102388
Design and Thermal-Hydraulic Performance Analysis of a Low-Temperature
Heat Pipe Test Facility
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  Authors: Ilyas Yilgor, Eymon Lan, Shanbin Shi
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-08-01T02:32:00Z
  DOI: 10.1080/00295639.2022.2087835
Validation and Uncertainty Quantification of Transient Reflood Models
Using COBRA-TF and Machine Learning Techniques Based on the NRC/PSU RBHT
Benchmark
Open Access Article
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  Authors: Yue Jin, Stephen M. Bajorek, Fan-Bill Cheung
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-07-28T03:56:06Z
  DOI: 10.1080/00295639.2022.2087834
Reactor Physics Experiment on a Graphite-Moderated Core to Construct
Integral Experiment Database for HTGR
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  Authors: Shoichiro Okita, Yuji Fukaya, Atsushi Sakon, Tadafumi Sano, Yoshiyuki Takahashi, Hironobu Unesaki
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-07-07T03:42:05Z
  DOI: 10.1080/00295639.2022.2087836
Pressure Drop in Seven-Pin Wire-Wrapped Rod Bundle for the Sodium
Cartridge Loop in Versatile Test Reactor
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  Authors: Zhengting Quan, Adam Dix, Ran Kong, Seungjin Kim, Mamoru Ishii, Mitchell T. Farmer
  Pages: 1 - 17
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-07-05T07:02:39Z
  DOI: 10.1080/00295639.2022.2082232
A Critical Review of Heat Pipe Experiments in Nuclear Energy Applications
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  Authors: Scott Wahlquist, Joshua Hansel, Piyush Sabharwall, Amir Ali
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-07-05T06:58:39Z
  DOI: 10.1080/00295639.2022.2082230
The Legendre Polynomial Axial Expansion Method
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  Authors: Nicholas F. Herring, Benjamin S. Collins, Thomas J. Downar, Aaron M. Graham
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-07-05T06:57:42Z
  DOI: 10.1080/00295639.2022.2082231
Asymptotic Diffusion Limits of the Multigroup Neutron Transport Equations
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  Authors: Edward W. Larsen
  Pages: 1 - 19
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-06-27T05:07:24Z
  DOI: 10.1080/00295639.2022.2058847
Frequency Transform Method for Transient Analysis of Nuclear Reactors in
Monte Carlo
Open Access Article
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  Authors: Miriam A. Kreher, Samuel Shaner, Benoit Forget, Kord Smith
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-06-10T02:30:18Z
  DOI: 10.1080/00295639.2022.2067739
Toward a More Realistic Analysis of Neutron Clustering
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  Authors: Thomas M. Sutton
  Pages: 1 - 12
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-05-20T03:40:31Z
  DOI: 10.1080/00295639.2022.2065872
Spatially Dependent Resonance Self-Shielding in CASMO5
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  Authors: Rodolfo M. Ferrer, Joshua M. Hykes
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-05-06T07:58:11Z
  DOI: 10.1080/00295639.2022.2053491
Flow-Induced Vibration of Solitary Wire-Wrapped Cylinders in Axial Flow
Open Access Article
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  Authors: Chad A. Nixon, Wade R. Marcum
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-04-29T03:41:06Z
  DOI: 10.1080/00295639.2022.2058846
Theoretical Derivation of a Unique Combination Number Hidden in the
Higher-Order Neutron Correlation Factors Using the Pál-Bell Equation
Open Access Article
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  Authors: Tomohiro Endo, Fuga Nishioka, Akio Yamamoto, Kenichi Watanabe, Cheol Ho Pyeon
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  Citation: Nuclear Science and Engineering
  PubDate: 2022-04-14T03:11:40Z
  DOI: 10.1080/00295639.2022.2049992